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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Dan Glenn, A. Sharif Heger, William B. Hladik III
Nuclear Technology | Volume 118 | Number 2 | May 1997 | Pages 142-150
Technical Paper | Radioisotopes and Isotopes | doi.org/10.13182/NT97-A35374
Articles are hosted by Taylor and Francis Online.
Nearly all the 99mTc administered to patients is obtained from eluting a radionuclide generator. The generators manufactured by the U.S. radiopharmaceutical companies use only the high-specific activity molybdenum produced by the fission of uranium. The dominant production methods are those used by Cintichem, Inc. and Nordion International. There are, however, competing methods of the production of fission-based 99Mo. One of the most promising proposed alternatives is the use of solution reactors (or homogeneous reactors). The operational characteristics of conventional reactors (i.e., Cintichem process) and those of solution reactors to produce 99Mo for use in manufacturing 99Mo/99mTc generators are examined. The use of conventional reactors has the disadvantage of generating large amounts of radioactive waste. The use of solution reactors can significantly reduce this problem. Both methods require rigorous processing to meet the purity requirements due to the presence of fission product contamination.